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In some situations, heat exchanger equipment is operated in a two-phase region beyond the critical heat flux point; e.g., fossil fueled boilers or steam generators, under steady conditions and nuclear reactor cores under transient conditions. Because of these and other similar situations there exists a continuing need for more accurate information about heat transfer coefficients in post-CHF flow regimes. Significant improvements in understanding have been made over the past few years. In particular, the development of experimental techniques has allowed the determination of the complete forced convection boiling curve including the "transition boiling" region for particular values of local vapor quality and mass velocity.
The objective of this section is to review the subject of Post-CHF heat transfer and indicate the "state-of-the-art." Although much of this work is specifically relevant to aqueous fluids the techniques used are beneficial in the design of other heat exchange equipment in the power and process industries.